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| Home > Publications database > C.A.S.H. - ein instationäres Anlagen-Rechenmodell für ein HTR-Modul-Kraftwerk : Benutzerhandbuch |
| Home > Publications database > C.A.S.H. - ein instationäres Anlagen-Rechenmodell für ein HTR-Modul-Kraftwerk : Benutzerhandbuch |
| Report | FZJ-2016-05964 |
; ;
1997
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/12739
Report No.: Juel-3403
Abstract: The Computer code C .A .S .H. has been developed as an integrated plant model for the HTR-Module reactor, in order to treat safety related questions about this type of power plant which require a det.ailed numerie simulation of the transient behaviour of the integrated plant. The simulation of the modular code system comprises the nuclear and thermo-hydraulic processes in the reactor, the two coolant loops with the heat exchanger, and the most important eomponents of the secondary loop. The guiding and control systems are mapped by modeling the block control system and the reactor protective system. The degree of detail of the subsystems, which are based on HTR codes developed in Juelich, permits statements about component loads and is characterised by : a two-dimensional thermo--hydraulics model of the core eoupled with the neutron dynamics by a special point kinetics model, a heat exchanger code representing the water/steam channel as a nonsteady two-phase-flow, the quasi steady-state computation of secondary loop components like live-steam live, turboset with control stage, and feed-water pump. The time dependent processes in the components are subdivided into plant time steps and are iteratively c:omputed in them. until consistency of the coolant loop statevariables by which they are coupled together . The four control loops for the bloch control of the Module are represented by digital filters ; the user can rum arbitrary plant transients by time dependent specification of their nominal values. By the application of the code System, safety technology statements can he acquired about the transient behaviour of Module reactors during power operations and in accidents, the influence of the guiding and control systems on the dynamics of the power plant can be analyzed, and safety-relevant component loads during transients can he established. The present report contains the user manual for this plant model. lt consists of three parts : In the first part, the code structure and: functions, the course of the simulation calculations, and important code parts are described. The second part is devoted to the practical application and explains extensively the handling of the cornplex code system with several sample calculations. These computing cases comprise load-follow transients and the shutdown procedure of the HTR Module and are presented and discussed with the full input data, job patterns, and nunierous computer graphics.The third part contains the input manual of C .A .S .H . and is rather extensive as it includes the complete inputs of several reactor component Computer codes along with the control program of the integrated plant model.
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